Replace all deprecated Python typing imports and syntax with updated …

…forms (openmc-dev#3085)

Co-authored-by: Paul Romano <[email protected]>

openmc/bounding_box.py

@@ -1,5 +1,5 @@
 from __future__ import annotations
-from typing import Iterable
+from collections.abc import Iterable
 
 import numpy as np
 

openmc/checkvalue.py

@@ -1,12 +1,11 @@
 import copy
 import os
-import typing  # required to prevent typing.Union namespace overwriting Union
 from collections.abc import Iterable
 
 import numpy as np
 
 # Type for arguments that accept file paths
-PathLike = typing.Union[str, os.PathLike]
+PathLike = str | os.PathLike
 
 
 def check_type(name, value, expected_type, expected_iter_type=None, *, none_ok=False):

openmc/data/data.py

@@ -5,7 +5,6 @@
 from pathlib import Path
 from math import sqrt, log
 from warnings import warn
-from typing import Dict
 
 # Isotopic abundances from Meija J, Coplen T B, et al, "Isotopic compositions
 # of the elements 2013 (IUPAC Technical Report)", Pure. Appl. Chem. 88 (3),
@@ -283,13 +282,13 @@
 NEUTRON_MASS = 1.00866491595
 
 # Used in atomic_mass function as a cache
-_ATOMIC_MASS: Dict[str, float] = {}
+_ATOMIC_MASS: dict[str, float] = {}
 
 # Regex for GNDS nuclide names (used in zam function)
 _GNDS_NAME_RE = re.compile(r'([A-Zn][a-z]*)(\d+)((?:_[em]\d+)?)')
 
 # Used in half_life function as a cache
-_HALF_LIFE: Dict[str, float] = {}
+_HALF_LIFE: dict[str, float] = {}
 _LOG_TWO = log(2.0)
 
 def atomic_mass(isotope):

openmc/data/decay.py

@@ -2,7 +2,6 @@
 from io import StringIO
 from math import log
 import re
-from typing import Optional
 from warnings import warn
 
 import numpy as np
@@ -579,7 +578,7 @@ def sources(self):
 _DECAY_PHOTON_ENERGY = {}
 
 
-def decay_photon_energy(nuclide: str) -> Optional[Univariate]:
+def decay_photon_energy(nuclide: str) -> Univariate | None:
     """Get photon energy distribution resulting from the decay of a nuclide
 
     This function relies on data stored in a depletion chain. Before calling it

openmc/deplete/coupled_operator.py

@@ -10,7 +10,6 @@
 
 import copy
 from warnings import warn
-from typing import Optional
 
 import numpy as np
 from uncertainties import ufloat
@@ -34,7 +33,7 @@
 __all__ = ["CoupledOperator", "Operator", "OperatorResult"]
 
 
-def _find_cross_sections(model: Optional[str] = None):
+def _find_cross_sections(model: str | None = None):
     """Determine cross sections to use for depletion
 
     Parameters

openmc/deplete/independent_operator.py

@@ -8,7 +8,6 @@
 from __future__ import annotations
 from collections.abc import Iterable
 import copy
-from typing import List, Set
 
 import numpy as np
 from uncertainties import ufloat
@@ -279,7 +278,7 @@ def _load_previous_results(self):
                 new_res = res_obj.distribute(self.local_mats, mat_indexes)
                 self.prev_res.append(new_res)
 
-    def _get_nuclides_with_data(self, cross_sections: List[MicroXS]) -> Set[str]:
+    def _get_nuclides_with_data(self, cross_sections: list[MicroXS]) -> set[str]:
         """Finds nuclides with cross section data"""
         return set(cross_sections[0].nuclides)
 

openmc/deplete/microxs.py

@@ -5,8 +5,8 @@
 """
 
 from __future__ import annotations
+from collections.abc import Iterable, Sequence
 from tempfile import TemporaryDirectory
-from typing import List, Tuple, Iterable, Optional, Union, Sequence
 
 import pandas as pd
 import numpy as np
@@ -27,7 +27,7 @@
 _valid_rxns.append('damage-energy')
 
 
-def _resolve_chain_file_path(chain_file: str):
+def _resolve_chain_file_path(chain_file: str | None):
     if chain_file is None:
         chain_file = openmc.config.get('chain_file')
         if 'chain_file' not in openmc.config:
@@ -41,12 +41,12 @@ def _resolve_chain_file_path(chain_file: str):
 def get_microxs_and_flux(
         model: openmc.Model,
         domains,
-        nuclides: Optional[Iterable[str]] = None,
-        reactions: Optional[Iterable[str]] = None,
-        energies: Optional[Union[Iterable[float], str]] = None,
-        chain_file: Optional[PathLike] = None,
+        nuclides: Iterable[str] | None = None,
+        reactions: Iterable[str] | None = None,
+        energies: Iterable[float] | str | None = None,
+        chain_file: PathLike | None = None,
         run_kwargs=None
-    ) -> Tuple[List[np.ndarray], List[MicroXS]]:
+    ) -> tuple[list[np.ndarray], list[MicroXS]]:
     """Generate a microscopic cross sections and flux from a Model
 
     .. versionadded:: 0.14.0
@@ -183,7 +183,7 @@ class MicroXS:
         :data:`openmc.deplete.chain.REACTIONS`
 
     """
-    def __init__(self, data: np.ndarray, nuclides: List[str], reactions: List[str]):
+    def __init__(self, data: np.ndarray, nuclides: list[str], reactions: list[str]):
         # Validate inputs
         if data.shape[:2] != (len(nuclides), len(reactions)):
             raise ValueError(
@@ -205,12 +205,12 @@ def __init__(self, data: np.ndarray, nuclides: List[str], reactions: List[str]):
     @classmethod
     def from_multigroup_flux(
         cls,
-        energies: Union[Sequence[float], str],
+        energies: Sequence[float] | str,
         multigroup_flux: Sequence[float],
-        chain_file: Optional[PathLike] = None,
+        chain_file: PathLike | None = None,
         temperature: float = 293.6,
-        nuclides: Optional[Sequence[str]] = None,
-        reactions: Optional[Sequence[str]] = None,
+        nuclides: Sequence[str] | None = None,
+        reactions: Sequence[str] | None = None,
         **init_kwargs: dict,
     ) -> MicroXS:
         """Generated microscopic cross sections from a known flux.

openmc/deplete/openmc_operator.py

@@ -7,7 +7,6 @@
 
 from abc import abstractmethod
 from warnings import warn
-from typing import List, Tuple, Dict
 
 import numpy as np
 
@@ -185,7 +184,7 @@ def _differentiate_burnable_mats(self):
         """Assign distribmats for each burnable material"""
         pass
 
-    def _get_burnable_mats(self) -> Tuple[List[str], Dict[str, float], List[str]]:
+    def _get_burnable_mats(self) -> tuple[list[str], dict[str, float], list[str]]:
         """Determine depletable materials, volumes, and nuclides
 
         Returns

openmc/deplete/reaction_rates.py

@@ -2,7 +2,6 @@
 
 An ndarray to store reaction rates with string, integer, or slice indexing.
 """
-from typing import Dict
 
 import numpy as np
 
@@ -53,9 +52,9 @@ class ReactionRates(np.ndarray):
     # the __array_finalize__ method (discussed here:
     # https://docs.scipy.org/doc/numpy/user/basics.subclassing.html)
 
-    index_mat: Dict[str, int]
-    index_nuc: Dict[str, int]
-    index_rx: Dict[str, int]
+    index_mat: dict[str, int]
+    index_nuc: dict[str, int]
+    index_rx: dict[str, int]
 
     def __new__(cls, local_mats, nuclides, reactions, from_results=False):
         # Create appropriately-sized zeroed-out ndarray

openmc/deplete/results.py

@@ -1,8 +1,7 @@
 import numbers
 import bisect
 import math
-import typing  # required to prevent typing.Union namespace overwriting Union
-from typing import Iterable, Optional, Tuple, List
+from collections.abc import Iterable
 from warnings import warn
 
 import h5py
@@ -97,11 +96,11 @@ def from_hdf5(cls, filename: PathLike):
 
     def get_activity(
         self,
-        mat: typing.Union[Material, str],
+        mat: Material | str,
         units: str = "Bq/cm3",
         by_nuclide: bool = False,
-        volume: Optional[float] = None
-    ) -> Tuple[np.ndarray, typing.Union[np.ndarray, List[dict]]]:
+        volume: float | None = None
+    ) -> tuple[np.ndarray, np.ndarray | list[dict]]:
         """Get activity of material over time.
 
         .. versionadded:: 0.14.0
@@ -152,11 +151,11 @@ def get_activity(
 
     def get_atoms(
         self,
-        mat: typing.Union[Material, str],
+        mat: Material | str,
         nuc: str,
         nuc_units: str = "atoms",
         time_units: str = "s"
-    ) -> Tuple[np.ndarray, np.ndarray]:
+    ) -> tuple[np.ndarray, np.ndarray]:
         """Get number of nuclides over time from a single material
 
         Parameters
@@ -215,11 +214,11 @@ def get_atoms(
 
     def get_decay_heat(
             self,
-            mat: typing.Union[Material, str],
+            mat: Material | str,
             units: str = "W",
             by_nuclide: bool = False,
-            volume: Optional[float] = None
-    ) -> Tuple[np.ndarray, typing.Union[np.ndarray, List[dict]]]:
+            volume: float | None = None
+    ) -> tuple[np.ndarray, np.ndarray | list[dict]]:
         """Get decay heat of material over time.
 
         .. versionadded:: 0.14.0
@@ -242,7 +241,7 @@ def get_decay_heat(
         -------
         times : numpy.ndarray
             Array of times in [s]
-        decay_heat : numpy.ndarray or List[dict]
+        decay_heat : numpy.ndarray or list[dict]
             Array of total decay heat values if by_nuclide = False (default)
             or list of dictionaries of decay heat values by nuclide if
             by_nuclide = True.
@@ -270,11 +269,11 @@ def get_decay_heat(
         return times, decay_heat
 
     def get_mass(self,
-        mat: typing.Union[Material, str],
+        mat: Material | str,
         nuc: str,
         mass_units: str = "g",
         time_units: str = "s"
-    ) -> Tuple[np.ndarray, np.ndarray]:
+    ) -> tuple[np.ndarray, np.ndarray]:
         """Get mass of nuclides over time from a single material
 
         .. versionadded:: 0.14.0
@@ -324,10 +323,10 @@ def get_mass(self,
 
     def get_reaction_rate(
         self,
-        mat: typing.Union[Material, str],
+        mat: Material | str,
         nuc: str,
         rx: str
-    ) -> Tuple[np.ndarray, np.ndarray]:
+    ) -> tuple[np.ndarray, np.ndarray]:
         """Get reaction rate in a single material/nuclide over time
 
         Parameters
@@ -364,7 +363,7 @@ def get_reaction_rate(
 
         return times, rates
 
-    def get_keff(self, time_units: str = 's') -> Tuple[np.ndarray, np.ndarray]:
+    def get_keff(self, time_units: str = 's') -> tuple[np.ndarray, np.ndarray]:
         """Evaluates the eigenvalue from a results list.
 
         .. versionadded:: 0.13.1
@@ -400,7 +399,7 @@ def get_keff(self, time_units: str = 's') -> Tuple[np.ndarray, np.ndarray]:
         times = _get_time_as(times, time_units)
         return times, eigenvalues
 
-    def get_eigenvalue(self, time_units: str = 's') -> Tuple[np.ndarray, np.ndarray]:
+    def get_eigenvalue(self, time_units: str = 's') -> tuple[np.ndarray, np.ndarray]:
         warn("The get_eigenvalue(...) function has been renamed get_keff and "
              "will be removed in a future version of OpenMC.", FutureWarning)
         return self.get_keff(time_units)
@@ -526,7 +525,7 @@ def get_step_where(
     def export_to_materials(
         self,
         burnup_index: int,
-        nuc_with_data: Optional[Iterable[str]] = None,
+        nuc_with_data: Iterable[str] | None = None,
         path: PathLike = 'materials.xml'
     ) -> Materials:
         """Return openmc.Materials object based on results at a given step